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The Symposium on Irradiation Effects on Structural Alloys for Nuclear Reactor Applications was presented at Niagara Falls, Canada, 29 June-1 July 1970, in conjunction with the Seventy-third Annual Meeting of the American Society for Testing and Materials held in Toronto, Ontario, Canada, 22-26 June 1970. The symposium was sponsored by ASTM Committee E10 on Radiosotopes and Radiation Effects. A. L. Bement, Jr., Battelle Memorial Institute, Pacific Northwest Laboratory, served as chairman of the symposium committee, which consisted of J. Moteff, cochairman, and K. M. Zwilsky, C. J. Baroch, E. Landerman, and L. E. Steele. The six sessions were presided over by L. J. Chockie, D. R. Harries, W. R. Thomas, R. Bullough, J. Moteff, and H. Bohm. Two agenda discussion sessions also were presented to survey the status of two contemporary problem areas.
Neutron Dosimetry for Reactor Pressure Vessel Applications
Morgan W., Serpan C.
Radiation Effects on the Metallurgical Fracture Parameters and Fracture Toughness of Pressure Vessel Steels
Ireland D., Tetelman A., Wullaert R.
The Effect of Hydrogen on the Ductile Properties of Irradiated Pressure Vessel Steels
Beeston J., Brinkman C.
Evaluation of the Embrittlement of Pressure Vessel Steels Irradiated in JPDR
Fujimura T., Kawasaki M., Namatame H., Suzuki K.
Neutron Irradiation Effects on Iron Containing Aluminum and Nitrogen
Hasiguti R., Igata N., Nishiike U., Watanabe K., Yagi E.
Effects of Irradiation in a Thermal Reactor on the Tensile Properties of Zircaloy 2 and 4 and Borated Stainless Steel
Baroch C., Harbinson E., Munim A.
Influence of Irradiation Temperature on the Tensile Properties of Stainless Steel
Bauer A., Kangilaski M., Spretnak J., Wullaert R.
The Mechanism and Kinetics of Void Growth During Neutron Irradiation
Bullough R., Perrin R.
Void Formation in Proton Irradiated Stainless Steel
Keefer D., Kramer D., Neely H., Pard A., Robinson J.
Considerations of Metal Swelling and Related Phenomena Caused by Fast Neutron Irradiation
Franklin D., Harkness S., Li C.
Neutron Dosimetry for Fast Reactor Applications
Dahl R., McElroy W.
Neutron Fluence Limit Determinations for Some Fast Flux Test Facility Components
Moen R., Thomas K., Tobin J.
Axial Fatigue of Irradiated Stainless Steels Tested at Elevated Temperatures
Beeston J., Brinkman C.
Effect of Irradiation on the Mechanical Properties of 19-9DL Alloy
Baroch C., Lowe A.
Influence of Neutron Irradiation on the Creep Rupture Properties of a 16Cr-13Ni Steel
Böhm H., Ehrlich K., Wassilew C.
The Effects of Helium on the High-Temperature Ductility of Sandvik 12R72HV and Inco IN-744X
Garr K., Kramer D., Pard A., Rhodes C.